Study of corrosion interaction of structural materials under high-dose irradiation;

Accumulation of different radionuclides.

Promising Areas of Research

Study of performance and behavior of structural, fuel and absorbing materials used in nuclear reactors of different applications (power reactors, propulsion reactors, research reactors, space reactors, etc.) under irradiation in design operating modes (standard, stationary, transient) and design basis accidents;

Development of techniques & devices and high-dose instrumented tests including creep tests, long-term strength tests and corrosion cracking of structural materials intended for next generation nuclear power facilities;